|
---|
Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] |
Text
November 25, 2019 Mr. Bryan C. Hanson Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION UNIT 2 REGULATORY AUDIT
SUMMARY
RE: CONFIRMATION OF A PLANTS IMPLEMENTATION OF NUCLEAR ENERGY INSTITUTE 19-02, GUIDANCE FOR ASSESSING OPEN PHASE CONDITION IMPLEMENTATION USING RISK INSIGHTS
Dear Mr. Hansen:
This letter is being sent to document the results of an audit conducted by the U.S. Nuclear Regulatory Commission (NRC) at Nine Mile Point Nuclear Station, Unit 2. The NRC conducted the audit according to the audit plan, Regulatory Audit in Support of Confirmation of a Plants Implementation of Nuclear Energy Institute (NEI) 19-02, Guidance for Assessing Open Phase Condition Implementation Using Risk Insights, (Agencywide Documents Access and Management System Accession No. ML19281D386). Nine Mile Point (NMP) 2 has decided to use NEI 19-02 to risk-inform the decision of whether to implement the Open Phase Isolation System to provide alarm and indication to the control room operators as opposed to automatic actuation mode in response to an Open Phase Condition (OPC). One of the purposes of the audit was to identify key areas to address in a revision to the Temporary Inspection (TI) on OPC response to accommodate a plant that chose to use NEI 19-02 to stay in alarm only mode to address an OPC. This was done by investigating whether NMP 2 appropriately implemented the guidance in NEI 19-02. The audit also helped to determine whether the implementation of NEI 19-02 could be an appropriate alternate approach consistent with the revised Voluntary Industry Initiative on OPC response. The audit took place from October 21th-October 24th, 2019. The audit team was comprised of a Reliability and Risk Analyst and an Electrical Engineer from NRC Headquarters.
The audit began on October 21st, 2019, with an entrance meeting between the NRC and the licensee's staff and contractors. During the audit, the NRC participated in a technical review according to the audit plan. This technical review focused on how the methodology described in NEI 19-02 was implemented and the application (or temporary changes) of the plant specific PRA model of record within the context of applying the 19-02 methodology. It also included reviewing the training conducted and procedures required to address OPC to help verify the Human Reliability Analysis (HRA) documented in the licensees assessment, as well as reviewing the supporting documentation behind other key assumptions described in the licensees assessment and PRA model.
On October 23rd, 2019, at the conclusion of the audit, the NRC participated in an exit meeting with the licensee's staff. During the exit, the NRC discussed recommendations that it would be incorporating into the revision of the TI. These recommendations included:
inspectors reviewing the training, procedures, and operator actions, and ensuring the
B.Hanson HRA described in NEI 19-02 matches the inspectors observations. Most importantly, inspectors should investigate the human action execution time described in the HRA. It was also identified that the revised TI would instruct the inspectors to verify assumptions listed in NEI 19-02, e.g. that the pump motors subjected to an OPC will be protected by their protective devices (especially if analysis indicates that failure will place them over the NEI 19-02 risk threshold). The team also identified that the NMP 2 HRA analysis was confusing (e.g., certain aspects of the HRA could have used more explanation, and there were incorrect graphs in one section due to a software error) and that moving forward, the HRA analysis in NEI 19-02 evaluations should be more clear. The team concluded that the audit did not identify any issues that would preclude NEI 19-02 from being an appropriate alternate approach consistent with the revised OPC Voluntary Industry Initiative. contains a list of documents reviewed by the team during the audit.
If you have any questions, please contact me at 301-415-8539 or via e-mail at Alexander.Schwab@nrc.gov.
Sincerely,
/RA/
Alexander H. Schwab, Reliability and Risk Analst PRA Oversight Branch Division of Risk Assessment Office of Nuclear Reactor Regulation
Enclosures:
- 1. List of Participants
- 2. List of Documents Reviewed cc: Listserv
LIST OF PARTICIPANTS U.S. Nuclear Regulatory Commission (NRC}Audit Team Alexander Schwab NRC/Audit Lead Hari Kodali NRC/Observer Enclosure 1
LIST OF DOCUMENTS REVIEWED DURING THE AUDIT The following documents were reviewed by the U.S. Nuclear Regulatory Commission (NRC) audit team during the audit. The documents generally included procedures that implement the actions described in response to an Open Phase Condition with the alarm in manual, the training on these procedures, the plants NEI 19-02 analysis, and other documentation verifying the assumptions used in the NEI 19-02 analysis.
- N2-MISC-015, Nine Mile Point Nuclear Station
- N2-ARP-852600, 2CEC*PNL852 Series 600 Alarm Response Procedures
- N-NM-OPS-2102-QS-04, Unit 2 Open Phase ARP Quick Set
- Analysis No. EC-205, Rev No. 000
- EC-154, Rev. 5 - Starting Voltage Verification or Class 1E MOVs
- EC-154, Rev. 5, Disposition No. 05A
- EC-154, Rev. 5, CCN No. ECP-09-000139 EC-154-05.000
- EC-154, Rev. 5, CCN No. 008521, Rev.0
- EC-166, Rev.0 - 4160 VAC Safety Related Breakers Coordination
- EC-166, Rev.0, Disposition No. 00B Enclosure 2
B. Hanson
SUBJECT:
NINE MILE POINT NUCLEAR STATION UNIT 2 REGULATORY AUDIT
SUMMARY
RE: CONFIRMATION OF A PLANTS IMPLEMENTATION OF NUCLEAR ENERGY INSTITUTE (NEI) 19-02, GUIDANCE FOR ASSESSING OPEN PHASE CONDITION IMPLEMENTATION USING RISK INSIGHTS DATED:
11/25/2019 DISTRIBUTION:
PUBLIC PM File Copy ASchwab, NRR AZoulis, NRR HKodali, NRR RidsNrrDraApob Resource RidsNrrDeEeob Resource ADAMS Accession No.: ML19329D261 *via email OFFICE NRR/DRA/APOB NRR/DRA/APOB*
NAME ASchwab AZoulis DATE 11/25/2019 11/21/2019